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High-temperature Hydrogen Permeation in Nickel Alloys

Description: In gas cooled Very High Temperature Reactor concepts, tritium is produced as a tertiary fission product and by activation of graphite core contaminants, such as lithium; of the helium isotope, He-3, that is naturally present in the He gas coolant; and the boron in the B4C burnable poison. Because of its high mobility at the reactor outlet temperatures, tritium poses a risk of permeating through the walls of the intermediate heat exchanger (IHX) or steam generator (SG) systems, potentially conta… more
Date: October 1, 2010
Creator: Calderoni, P.; Ebner, M. & Pawelko, R.
Partner: UNT Libraries Government Documents Department
open access

Measurement of tritium permeation in flibe (2LiF•BeF2)

Description: This paper reports on the experimental investigation of tritium permeation in flibe (2LiF-BeF2) at the Safety and Tritium Applied Research facility of the Idaho National Laboratory. A stainless steel cell formed by two independent volumes separated by a 2mm thick nickel membrane is maintained at temperatures between 500 and 700 degrees Celsius. A controlled amount of T2 gas is flown in excess of argon in the source volume in contact with the bottom side of the nickel membrane, while a layer of … more
Date: October 1, 2007
Creator: Calderoni, P.; Sharpe, P.; Hara, M. & Oya, Y.
Partner: UNT Libraries Government Documents Department
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Overview of Recent Tritium Experiments in TPE

Description: Tritium retention in plasma-facing components influences the design, operation, and lifetime of fusion devices such as ITER. Most of the retention studies were carried out with the use of either hydrogen or deuterium. Tritium Plasma Experiment is a unique linear plasma device that can handle radioactive fusion fuel of tritium, toxic material of beryllium, and neutron-irradiated material. A tritium depth profiling method up to mm range was developed using a tritium imaging plate and a diamond wi… more
Date: October 1, 2010
Creator: Shimada, Masashi; Otsuka, T.; Pawelko, R. J.; Calderoni, P. & Sharpe, J. P.
Partner: UNT Libraries Government Documents Department
open access

Deuterium Depth Profile in Neutron-Irradiated Tungsten Exposed to Plasma

Description: The effect of radiation damage has been mainly simulated using high-energy ion bombardment. The ions, however, are limited in range to only a few microns into the surface. Hence, some uncertainty remains about the increase of trapping at radiation damage produced by 14 MeV fusion neutrons, which penetrate much farther into the bulk material. With the Japan-US joint research project: Tritium, Irradiations, and Thermofluids for America and Nippon (TITAN), the tungsten samples (99.99 % pure from A… more
Date: May 1, 2011
Creator: Shimada, Masashi; Cao, G.; Hatano, Y.; Oda, T.; Oya, Y.; Hara, M. et al.
Partner: UNT Libraries Government Documents Department
open access

Overview of the US-Japan collaborative investigation on hydrogen isotope retention in neutron-irradiated and ion-damaged tungsten

Description: Plasma-facing components (PFCs) will be exposed to 14 MeV neutrons from deuterium-tritium (D-T) fusion reactions, and tungsten, a candidate PFC for the divertor in ITER, is expected to receive a neutron dose of 0.7 displacement per atom (dpa) by the end of operation in ITER. The effect of neutron-irradiation damage has been mainly simulated using high-energy ion bombardment. While this prior database of results is quite valuable for understanding the behavior of hydrogen isotopes in PFCs, it do… more
Date: September 1, 2011
Creator: Shimada, Masashi; Hatano, Y.; Oya, Y.; Oda, T.; Hara, M.; Cao, G. et al.
Partner: UNT Libraries Government Documents Department
open access

An overview of dual coolant Pb-17Li breeder first wall and blanket concept development for the US ITER-TBM design

Description: An attractive blanket concept for the fusion reactor is the dual coolant Pb-17Li liquid (DCLL) breeder design. Reduced activation ferritic steel (RAFS) is used as the structural material. Helium is used to cool the first wall and blanket structure, and the self-cooled breeder Pb-17Li is circulated for power conversion and for tritium breeding. A SiCf/SiC composite insert is used as the magnetohydrodynamic (MHD) insulation to reduce the impact from the MHD pressure drop of the circulating Pb-17L… more
Date: May 13, 2005
Creator: Wong, C. C.; Malang, S.; Sawan, M.; Dagher, M.; Smolentsev, S.; Merrill, B. et al.
Partner: UNT Libraries Government Documents Department
open access

IFE Thick Liquid Wall Chamber Dynamics: Governing Mechanisms and Modeling and Experimental Capabilities

Description: For thick liquid wall concepts, it is important to understand the different mechanisms affecting the chamber dynamics and the state of the chamber prior to each shot a compared with requirements from the driver and target. These include ablation mechanisms, vapor transport and control, possible aerosol formation, as well as protective jet behavior. This paper was motivated by a town meeting on this subject which helped identify the major issues, assess the latest results, review the capabilitie… more
Date: January 24, 2005
Creator: Raffray, A. R.; Meier, W.; Abdel-Khalik, S.; Bonazza, R.; Calderoni, P.; Debonnel, C. S. et al.
Partner: UNT Libraries Government Documents Department
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